skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Elevated Temperature Tensile Tests on DU–10Mo Rolled Foils

Abstract

Tensile mechanical properties for uranium-10 wt.% molybdenum (U–10Mo) foils are required to support modeling and qualification of new monolithic fuel plate designs. It is expected that depleted uranium-10 wt% Mo (DU–10Mo) mechanical behavior is representative of the low enriched U–10Mo to be used in the actual fuel plates, therefore DU-10Mo was studied to simplify material processing, handling, and testing requirements. In this report, tensile testing of DU-10Mo fuel foils prepared using four different thermomechanical processing treatments were conducted to assess the impact of foil fabrication history on resultant tensile properties.

Authors:
 [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1183495
Report Number(s):
INL/EXT-14-33639
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; fuel foils; tensile strenght; U-Mo

Citation Formats

Schulthess, Jason. Elevated Temperature Tensile Tests on DU–10Mo Rolled Foils. United States: N. p., 2014. Web. doi:10.2172/1183495.
Schulthess, Jason. Elevated Temperature Tensile Tests on DU–10Mo Rolled Foils. United States. doi:10.2172/1183495.
Schulthess, Jason. Mon . "Elevated Temperature Tensile Tests on DU–10Mo Rolled Foils". United States. doi:10.2172/1183495. https://www.osti.gov/servlets/purl/1183495.
@article{osti_1183495,
title = {Elevated Temperature Tensile Tests on DU–10Mo Rolled Foils},
author = {Schulthess, Jason},
abstractNote = {Tensile mechanical properties for uranium-10 wt.% molybdenum (U–10Mo) foils are required to support modeling and qualification of new monolithic fuel plate designs. It is expected that depleted uranium-10 wt% Mo (DU–10Mo) mechanical behavior is representative of the low enriched U–10Mo to be used in the actual fuel plates, therefore DU-10Mo was studied to simplify material processing, handling, and testing requirements. In this report, tensile testing of DU-10Mo fuel foils prepared using four different thermomechanical processing treatments were conducted to assess the impact of foil fabrication history on resultant tensile properties.},
doi = {10.2172/1183495},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Sep 01 00:00:00 EDT 2014},
month = {Mon Sep 01 00:00:00 EDT 2014}
}

Technical Report:

Save / Share: